96-Cm-245(n,f)

Requester

Prof. Massimo SALVATORES at CADARACHE, FR

Project (context)

NEA WPEC Subgroup 26

Impact

Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

Requested accuracy is required to meet target accuracies for k_eff, peak power and burnup for the Accelerator-Driven Minor Actinides Burner (ADMAB). Details are provided in the OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb ).

Accuracy

Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties.

Justification document

OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb ).

Comment from requester

Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Entry status

Work in progress (as of SG-C review of May 2018)

Main recent references

Please report any missing information to hprlinfo@oecd-nea.org

Experiments

• O. Serot et al., Measurement of the Neutron Induced Fission of 245Cm in the Resolved Resonance Region and Its Resonance Analysis, Journal of the Korean Physical Society 59 (2011) 1896, EXFOR 23120
• K. Hirose et al., Fission cross-section measurements of 237Np, 242mAm, and 245Cm with lead slowing-down neutron spectrometer, JNST 49 (2012) 1057, EXFOR 23186
• M. Calviani, et al., Neutron-induced fission cross section of 245Cm: New results from data taken at the time-of-flight facility n_TOF, PRC 85 (2012) 034616, EXFOR 23168

Theory/Evaluation

• K. Shibata et al., JENDL-4.0: A New Library for Nuclear Science and Engineering, J. Nucl. Sci. Technol. 48 (2011) 1

Validation

• G. Palmiotti, et al., Combined Use of Integral Experiments and Covariance Data, Nuclear Data Sheets 118 (2014) 596